US2024289517A1PendingUtilityA1
Method, device and computer-readable storage medium for implementing magnetic confinement reaction
Assignee: HEFEI INST PHYSICAL SCI CASPriority: Sep 28, 2023Filed: Apr 29, 2024Published: Aug 29, 2024
Est. expirySep 28, 2043(~17.2 yrs left)· nominal 20-yr term from priority
G21B 1/11G21B 1/05G21B 1/057G06F 30/20Y02E30/10G06F 2111/10G21B 1/13G06F 30/367
58
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Claims
Abstract
A method for implementing a magnetic confinement reaction is provided. An initial equilibrium configuration is constructed based on zero-dimensional parameters. The initial equilibrium configuration is subjected to iteration with a blanket, a divertor and a magnet to determine an equilibrium configuration of a reference equilibrium. A numerical simulation model of a plasma breakdown phase in a start-up process is established using a rigid conductor, and optimally solved to determine a maximum coil current. A phase after the breakdown is optimized into a quadratic programing problem to establish a performance function, which is solved using a preset constraint to determine a to-be-optimized parameter. The start-up process of the superconducting tokamak is completed according to the equilibrium configuration, the maximum coil current and the to-be-optimized parameter. A device and computer-readable storage medium for implementing magnetic confinement reaction are also provided.
Claims
exact text as granted — not AI-modifiedWhat is claimed is:
1 . A method for implementing a magnetic confinement reaction, comprising:
step (1) constructing an initial equilibrium configuration based on zero-dimensional parameters; step (2) subjecting the initial equilibrium configuration to iteration with a blanket, a divertor and a magnet to determine an equilibrium configuration corresponding to a reference equilibrium; step (3) establishing a numerical simulation model of a plasma breakdown phase in a start-up process using a rigid conductor, and optimally solving the numerical simulation model to determine a maximum coil current; step (4) optimizing a phase in the start-up process after the plasma breakdown phase into a quadratic programing problem to establish a performance function, and solving the performance function using a preset constraint to determine a to-be-optimized parameter; and step (5) completing the start-up process of a superconducting tokamak according to the equilibrium configuration, the maximum coil current and the to-be-optimized parameter.
2 . The method of claim 1 , wherein the zero-dimensional parameters comprise plasma current, major radius, minor radius, elongation ratio, 95-plane elongation ratio, triangularity, 95-plane triangularity, top triangularity, bottom triangularity, volume, inner leg length of the divertor and outer leg length of the divertor.
3 . The method of claim 1 , wherein the step (3) is performed through steps of:
establishing the numerical simulation model of the plasma breakdown phase using the rigid conductor; setting a voltage of a poloidal field coil to change piecewise and linearly, and converting the numerical simulation model into an integrated model; designing a maximum excitation current and an initial zero-field optimization to convert the integrated model into a given performance function; and solving the given performance function by linear least-square fitting according to given device parameters to obtain an excitation current of the poloidal field coil as the maximum coil current; wherein a circuit equation of active coils of the numerical simulation model is expressed as:
M
cc
dI
c
dt
+
R
c
I
c
+
M
cv
dI
v
dt
=
V
c
,
and a circuit equation of passive conductors of the numerical simulation model is expressed as:
M
vv
dI
v
dt
+
R
v
I
v
+
M
cv
dI
c
dt
=
0
;
wherein M cc is a mutual inductance between the active coils, M vv is a mutual inductance between the passive conductors, M cv is a mutual inductance between the active coils and the passive conductors, R c is a resistance of each of the active coils, R v is a resistance of each of the passive conductors, I c is a current on each of the active coils, I v is a current on each of the passive conductors, and V c is a voltage across each of the active coils;
the integrated model is expressed as:
M
I
.
+
RI
=
V
0
+
V
.
0
t
;
wherein M is a mutual inductance matrix, R is a resistance vector, I is a current vector, V 0 is a voltage vector at time t 0 , İ is a conductor current change rate, {dot over (V)} 0 is a voltage change rate at the time t 0 , and {dot over (V)} 0 is expressed as:
V
.
0
=
V
1
-
V
0
t
1
-
t
0
,
wherein V 1 is a voltage vector at time t 1 ;
the given performance function is expressed as:
F
(
I
i
)
=
❘
"\[LeftBracketingBar]"
ψ
0
-
∑
n
c
i
=
1
M
ci
I
i
B
z
1
-
∑
n
c
i
=
1
G
c
1
i
I
i
B
z
2
-
∑
n
c
i
=
1
G
c
2
i
I
i
⋮
B
zn
pt
-
∑
n
c
i
=
1
G
cn
pt
i
I
i
❘
"\[RightBracketingBar]"
;
wherein n c is the number of loops of the poloidal field coil, ψ 0 is a magnetic flux at a plasma breakdown center, B z1 −B zn pt are magnetic fields in plasma optimization areas, G c1i −G cn pt i are Green's functions of the passive conductors versus plasma optimization areas, n pt is the number of the plasma optimization areas, M ci is a mutual inductance coefficient matrix of the passive conductors versus the plasma optimization areas, I i is a to-be-determined coil current, and F(I i ) is a to-be-optimized performance function;
the given device parameters comprise coordinates of the plasma breakdown center, a size of a vacuum chamber, a maximum number of volt seconds provided by the poloidal field coil, a current limit of the poloidal field coil, a maximum current change rate and a terminal voltage limit of the poloidal field coil.
4 . The method of claim 1 , wherein the performance function is expressed as:
F
(
V
)
=
∑
(
Φ
_
i
-
Φ
i
tgt
)
2
;
wherein V is a coil voltage ratio, Φ i tgt is a target value of plasma parameters, comprising loop voltage, vertical field intensity and current ramp-up rate, Φ i is an optimized calculated value of a corresponding plasma parameter, i is a subscript of a to-be-determined plasma parameter, and F(V) is an optimized performance function; and
the preset constraints comprise preset coil parameters and power supply parameters, and the to-be-optimized parameter comprises zero-field distribution, vertical field distribution, loop voltage value and initial rising waveform of a plasma current.
5 . The method of claim 1 , further comprising:
driving a plasma using a radio-frequency current distributed in a radial direction, and enhancing a local reversed magnetic shear structure in a safety factor profile to optimize a local magnetic shear.
6 . The method of claim 1 , further comprising:
simulating a state after plasma breakdown with preset parameters, wherein the preset parameters comprise an initial plasma current, an initial equilibrium point and an initial configuration; monitoring a magnetic flux change at a preset observation point followed by feeding back to a feedback control system, wherein the magnetic flux change comprises a polar position and a vertical position; controlling, by the feedback control system, an early shaped discharge mode of the plasma to maintain a configuration equilibrium of the plasma; and heating the plasma with an auxiliary heating power of 20 MW, wherein the auxiliary heating power consists of 10 MW of ion cyclotron wave heating and 10 MW of neutral beam heating, and additionally introducing 2 MW of low-hybrid wave heating during a ramp-up phase, so as to achieve a mixed operation mode.
7 . The method of claim 1 , further comprising:
simulating a state after plasma breakdown with preset parameters, wherein the preset parameters comprise an initial plasma current, an initial equilibrium point and an initial configuration; and heating plasma with 15 MW of ion cyclotron wave heating, 10 MW of low hybrid wave heating and 6 MW of neutral beam heating, so as to achieve a steady-state operation mode.
8 . A device for implementing a magnetic confinement reaction, comprising:
a constructing module; an iteration module; a first solving module; a second solving module; and a breakdown start-up module; wherein the constructing module is configured to construct an initial equilibrium configuration based on zero-dimensional parameters; the iteration module is configured to determine an equilibrium configuration of a reference equilibrium after iterating with a blanket, a divertor and a magnet; the first solving module is configured to establish a numerical simulation model of a plasma breakdown phase in a start-up process using a rigid conductor, and optimally solve the numerical simulation model to determine a maximum coil current; the second solving module is configured to optimize a phase in the start-up process after the plasma breakdown phase into a quadratic programming problem to establish a performance function, and solve the performance function using a preset constraint to determine a to-be-optimized parameter; and the breakdown start-up module is configured to complete the start-up process of a superconducting tokamak according to the equilibrium configuration, the maximum coil current and the to-be-optimized parameter.
9 . A terminal equipment, comprising:
a processor; a memory; and a computer program; wherein the computer program is stored in the memory, and is configured to be executed by the processor; and the processor is configured to execute the computer program to implement the method of claim 1 .
10 . A computer-readable storage medium, wherein a computer program is stored on the computer-readable storage medium; and the computer program is configured to be executed to control a device equipped with the computer-readable storage medium to implement the method of claim 1 .Join the waitlist — get patent alerts
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